scholarly journals Identification and Assessment of Material Models for Age-Related Degradation of Structures and Passive Components in Nuclear Power Plants

2009 ◽  
Author(s):  
J. Nie ◽  
J. Braverman ◽  
C. Hofmayer ◽  
M. K. Kim ◽  
I-K. Choi
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Material Models ◽  
Passive Components ◽  
Age Related

Degradation assessment of structures and passive components at nuclear power plants

2004 ◽  
Vol 228 (1-3) ◽  
pp. 283-304 ◽  
Author(s):  
J.I. Braverman ◽  
C.A. Miller ◽  
C.H. Hofmayer ◽  
B.R. Ellingwood ◽  
D.J. Naus ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Passive Components

Online Monitoring and Prognostics for Passive Components in Nuclear Power Plants

2016 ◽  
Vol 182 (2) ◽  
pp. 228-242 ◽  
Author(s):  
Pradeep Ramuhalli ◽  
Surajit Roy ◽  
Jangbom Chai
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Online Monitoring ◽  
Passive Components

Adaptive fuzzy system for degradation study in nuclear power plants' passive components

2006 ◽  
Vol 48 (7) ◽  
pp. 655-663 ◽  
Author(s):  
Antônio César Ferreira Guimarães ◽  
Denise Cunha Cabral ◽  
Celso Marcelo Franklin Lapa
Keyword(s):  
Fuzzy System ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Passive Components ◽  
Degradation Study ◽  
Adaptive Fuzzy ◽  
Adaptive Fuzzy System

Seismic Fragility Analysis of a Condensate Storage Tank With Multiple Uncertain Degradation Scenarios

2012 ◽  
Author(s):  
Jinsuo R. Nie ◽  
Joseph I. Braverman ◽  
Charles H. Hofmayer ◽  
Young-Sun Choun ◽  
Min Kyu Kim ◽  
...  
Keyword(s):  
Storage Tank ◽  
Nuclear Power ◽  
Power Plants ◽  
National Laboratory ◽  
Brookhaven National Laboratory ◽  
Fragility Analysis ◽  
Seismic Fragility ◽  
Passive Components ◽  
Age Related ◽  
Effects Of Aging

The Korea Atomic Energy Research Institute (KAERI) and Brookhaven National Laboratory (BNL) are continuing a collaborative effort to achieve a better understanding of the effects of aging on the performance of structures and passive components (SPCs) in nuclear power plants (NPPs). This paper presents a seismic fragility analysis of a condensate storage tank (CST) with multiple degradation scenarios that are treated in a non-perfectly correlated manner. The analysis utilizes a set of optimum Latin Hypercube samples to characterize the deterioration behavior of the fragility capacity as a function of age-related degradations. This study is an addition to the previous study summarized in an ICONE19 paper entitled “Seismic Fragility Analysis of a Degraded Condensate Storage Tank” [1], which considered individual degradation scenarios and multiple degradations occurring in a perfectly correlated manner.

scholarly journals Review of Recent Aging-Related Degradation Occurrences of Structures and Passive Components in U.S. Nuclear Power Plants

2009 ◽  
Author(s):  
Jinsuo Nie ◽  
Joseph I. Braverman ◽  
Charles H. Hofmayer ◽  
Young-Sun Choun ◽  
Min Kyu Kim ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Research Effort ◽  
National Laboratory ◽  
Brookhaven National Laboratory ◽  
Piping System ◽  
Passive Components ◽  
The Status ◽  
Capability Evaluation

The Korea Atomic Energy Research Institute (KAERI) and Brookhaven National Laboratory (BNL) are collaborating to develop seismic capability evaluation technology for degraded structures and passive components (SPCs) under a multi-year research agreement. To better understand the status and characteristics of degradation of SPCs in nuclear power plants (NPPs), the first step in this multi-year research effort was to identify and evaluate degradation occurrences of SPCs in U.S. NPPs. This was performed by reviewing recent publicly available information sources to identify and evaluate the characteristics of degradation occurrences and then comparing the information to the observations in the past. Ten categories of SPCs that are applicable to Korean NPPs were identified, comprising of anchorage, concrete, containment, exchanger, filter, piping system, reactor pressure vessel, structural steel, tank, and vessel. Software tools were developed to expedite the review process. Results from this review effort were compared to previous data in the literature to characterize the overall degradation trends.

Evaluation of Concrete Structures Using Nondestructive Techniques

2012 ◽  
Author(s):  
Hemant S. Limaye
Keyword(s):  
Nondestructive Testing ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Concrete Structures ◽  
Structural Components ◽  
Age Related ◽  
Need To Evaluate ◽  
New Construction ◽  
Deterioration Assessment

To renew the expiring licenses of the nuclear power plants, the operators will need to evaluate major structural components for the age related deterioration. Assessment of the interior of the concrete structures can be made using the available nondestructive testing (NDT) methods. This paper presents a quick overview of the methods and describes how some of these methods were used for the two projects-one for the new construction and one for the existing project going through the modification/renovation.

Test Programs for Degraded Core Shroud and PLR Piping: Simulated Crack Models and Input Seismic Waves for Shaking Test

2006 ◽  
Author(s):  
Kenichi Suzuki ◽  
Hidefumi Kawauchi ◽  
Hiroshi Abe
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Seismic Waves ◽  
Response Spectra ◽  
Shaking Table ◽  
Seismic Safety ◽  
Age Related ◽  
Test Models ◽  
Core Shroud

Since the age-related degradation of structures and components in nuclear power plants has been a key issue regarding assessments of seismic safety, the Japan Nuclear Energy Safety Organization (JNES) initiated seismic test programs in fiscal 2004 for the degraded core shroud and primary loop recirculation (PLR) system piping used in old BWR plants. The objectives were to: i) obtain a better understanding of the vibration characteristics and seismic strength of degraded structures and components having cracks due to aging, ii) ensure a margin of seismic design safety by considering age-related cracking, and iii) verify the JSME Code Rules on Fitness-for-Service for Nuclear Power Plants in Japan. Plans were made to test the components of the core shroud and PLR system piping under quasi-static displacement control of monotonous and cyclic load conditions. Plans were also made to test combined components on a shaking table by using a 1/2.5-scale core shroud model and an approximately 1/3-scale PLR piping model. All test models were designed to contain simulated cracking due to aging, involving cracks assumed to have the maximum allowable size according to the JSME Code Rules. The input seismic waves were prepared for the combined component tests of the scaled models based on a modified envelope of broadened response spectra of all S2 design seismic waves in Japan. Final evaluation of the simulated crack models and input seismic waves used for the tests will be conducted in fiscal 2005.

Development of Guideline on Seismic Fragility Evaluation for Aged Piping

2021 ◽  
Author(s):  
Yoshihito Yamaguchi ◽  
Jinya Katsuyama ◽  
Koichi Masaki ◽  
Yinsheng Li
Keyword(s):  
Risk Assessment ◽  
Fracture Mechanics ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Seismic Fragility ◽  
Degradation Mechanisms ◽  
Probabilistic Fracture Mechanics ◽  
Age Related ◽  
Piping Systems

Abstract The seismic probabilistic risk assessment is an important methodology to evaluate the seismic safety of nuclear power plants. In this assessment, the core damage frequency is evaluated from the seismic hazard, seismic fragilities, and accident sequence. Regarding the seismic fragility evaluation, the probabilistic fracture mechanics can be applied as a useful evaluation technique for aged piping systems with crack or wall thinning due to the age-related degradation mechanisms. In this study, to advance seismic probabilistic risk assessment methodology of nuclear power plants that have been in operation for a long time, a guideline on the seismic fragility evaluation of the typical aged piping systems of nuclear power plants has been developed considering the age-related degradation mechanisms. This paper provides an outline of the guideline and several examples of seismic fragility evaluation based on the guideline and utilizing the probabilistic fracture mechanics analysis code.

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